Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect

doi:10.1016/j.jnucmat.2022.153629

IMR OpenIR

	Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect
	Wu, Bin 1,2; Ming, Hongliang 1,2; Zhang, Zhiming 3; Meng, Fanjiang 4; He, Guangqing 5,6; Wang, Jianqiu 1,2,3; Han, En-Hou 1,3
通讯作者	Ming, Hongliang(hlming12s@imr.ac.cn) ; Meng, Fanjiang(mengfanjiang@snerdi.com.cn)
	2022-05-01
发表期刊	JOURNAL OF NUCLEAR MATERIALS
ISSN	0022-3115
卷号	563 页码:14
摘要	S C Alloy 690TT tube samples with different sizes of internal bulge defect (IBD) are prepared by actual hydraulic tube expansion in field and their microstructure and stress corrosion cracking (SCC) behavior are studied in detail. The hardening level and residual strain increase as moving from the original area of the tube to the bulged area, and so as for the increasing of deformation sizes. Corrosion test with a duration of 20 0 0 h shows that the IBD area has higher SCC sensitivity than the original tube. In addition, IBD with larger size is more sensitive to SCC. (c) 2022 Elsevier B.V. All rights reserved.
关键词	Alloy 690TT Tube expansion Internal bulge defect Stress corrosion cracking Intergranular corrosion High temperature corrosion
资助者	Youth Innovation Promo-tion Association CAS ; National Natural Science Foun-dation of China ; National Key RD Program ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)
DOI	10.1016/j.jnucmat.2022.153629
收录类别	SCI
语种	英语
资助项目	Youth Innovation Promo-tion Association CAS[2022187] ; National Natural Science Foun-dation of China[51771211] ; National Key RD Program[2019YFB1900904] ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)[2021NMSAKF01] ; CAS Key lab-oratory of Nuclear Materials and Safety Assessment (Instituteof Metal Research, Chinese Academy of Sciences , China)[2022NMSAKF03]
WOS研究方向	Materials Science ; Nuclear Science & Technology
WOS类目	Materials Science, Multidisciplinary ; Nuclear Science & Technology
WOS记录号	WOS:000793200400006
出版者	ELSEVIER
引用统计	被引频次：6[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/173930
专题	中国科学院金属研究所
通讯作者	Ming, Hongliang; Meng, Fanjiang
作者单位	1.Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 2.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China 3.Inst Corros Sci & Technol, Guangzhou 510530, Peoples R China 4.Shanghai Nucl Engn Res & Design Inst Ltd Co, Shanghai 200233, Peoples R China 5.Fudan Univ, Dept Mat Sci, Shanghai 200433, Peoples R China 6.Shanghai Elect Nucl Power Equipment Co Ltd, Shanghai 201306, Peoples R China
推荐引用方式 GB/T 7714	Wu, Bin,Ming, Hongliang,Zhang, Zhiming,et al. Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect[J]. JOURNAL OF NUCLEAR MATERIALS,2022,563:14.
APA	Wu, Bin.,Ming, Hongliang.,Zhang, Zhiming.,Meng, Fanjiang.,He, Guangqing.,...&Han, En-Hou.(2022).Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect.JOURNAL OF NUCLEAR MATERIALS,563,14.
MLA	Wu, Bin,et al."Microstructure and stress corrosion cracking behavior of Alloy 690TT steam generator tubes with internal bulge defect".JOURNAL OF NUCLEAR MATERIALS 563(2022):14.